Post-implementation review of inadequate core cooling instrumentation
Conference
·
· IEEE Trans. Nucl. Sci.; (United States)
OSTI ID:6300263
Studies of the Three Mile Island (TMI) accident identified the need for additional instrumentation to detect inadequate core cooling (ICC) in nuclear power plants. NRC Regulatory Guide 1.97, which covers accident monitoring instrumentation, was revised to be consistent with the requirements of item II.F.2 of NUREG-0737. Following are some of the more significant requirements specified in that item. Instrumentation should provide an unambiguous indication of the approach to and existence of ICC. Reactor water level measurement is to be considered. The system must indicate the existence of ICC caused by various phenomena (e.g., high void fraction pumped flow and stagnant boil-off). The presence of an unrelated phenomenon must not cause the system to erroneously indicate ICC. Advance warning of the approach of ICC must be given. Instrumentation must conform to Appendix B (Class 1E) of NUREG-0737. Alarms and displays should be selected based on a human factors analysis. Instrumentation indications must be integrated into emergency procedures and operator training programs.
- Research Organization:
- Oak Ridge National Lab., Oak Ridge, TN (US)
- OSTI ID:
- 6300263
- Report Number(s):
- CONF-881103-
- Conference Information:
- Journal Name: IEEE Trans. Nucl. Sci.; (United States) Journal Volume: 36:1
- Country of Publication:
- United States
- Language:
- English
Similar Records
Instrument accuracy in reactor vessel inventory tracking systems
Primary coolant pump measurement for ICC trend analysis
Summary of inadequate core cooling instrumentation for US nuclear power plants
Conference
·
Tue Dec 31 23:00:00 EST 1985
·
OSTI ID:5507684
Primary coolant pump measurement for ICC trend analysis
Conference
·
Sat Dec 31 23:00:00 EST 1983
·
OSTI ID:5999300
Summary of inadequate core cooling instrumentation for US nuclear power plants
Technical Report
·
Sun Jul 01 00:00:00 EDT 1990
·
OSTI ID:6791562
Related Subjects
21 SPECIFIC NUCLEAR REACTORS AND ASSOCIATED PLANTS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALARM SYSTEMS
COOLING
DOCUMENT TYPES
EMERGENCY PLANS
ENRICHED URANIUM REACTORS
IMPLEMENTATION
MEASURING INSTRUMENTS
MINIMIZATION
MONITORING
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERSONNEL
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
REGULATIONS
REVIEWS
SAFETY
THERMAL POWER PLANTS
THERMAL REACTORS
THERMOCOUPLES
THREE MILE ISLAND-1 REACTOR
TRAINING
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS
210200 -- Power Reactors
Nonbreeding
Light-Water Moderated
Nonboiling Water Cooled
22 GENERAL STUDIES OF NUCLEAR REACTORS
220400 -- Nuclear Reactor Technology-- Control Systems
220900* -- Nuclear Reactor Technology-- Reactor Safety
ACCIDENTS
ALARM SYSTEMS
COOLING
DOCUMENT TYPES
EMERGENCY PLANS
ENRICHED URANIUM REACTORS
IMPLEMENTATION
MEASURING INSTRUMENTS
MINIMIZATION
MONITORING
NATIONAL ORGANIZATIONS
NUCLEAR FACILITIES
NUCLEAR POWER PLANTS
PERSONNEL
POWER PLANTS
POWER REACTORS
PWR TYPE REACTORS
REACTOR ACCIDENTS
REACTOR COMPONENTS
REACTOR CORES
REACTOR SAFETY
REACTORS
REGULATIONS
REVIEWS
SAFETY
THERMAL POWER PLANTS
THERMAL REACTORS
THERMOCOUPLES
THREE MILE ISLAND-1 REACTOR
TRAINING
US NRC
US ORGANIZATIONS
WATER COOLED REACTORS
WATER MODERATED REACTORS